ML19266A527
| ML19266A527 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron, Braidwood, Clinton, Quad Cities, FitzPatrick, LaSalle |
| Issue date: | 10/08/2019 |
| From: | Blake Purnell Plant Licensing Branch III |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Purnell B | |
| References | |
| EPID L-2018-LLA-0297 | |
| Download: ML19266A527 (102) | |
Text
Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 8, 2019 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; JAMES A. FITZPATRICK NUCLEAR POWER PLANT; LASALLE COUNTY STATION, UNITS 1 AND 2; AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2-ISSUANCE OF AMENDMENTS TO ELIMINATE SECOND COMPLETION TIMES FROM TECHNICAL SPECIFICATIONS (EPID L-2018-LLA-0297)
Dear Mr. Hanson:
The U.S. Nuclear Regulatory Commission (NRC) has issued the following enclosed amendments in response to the Exelon Generation Company, LLC (Exelon, the licensee) application dated November 1, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML183056401):
- 1.
Amendment No. 203 to Renewed Facility Operating License No. NPF-72 and Amendment No. 203 to Renewed Facility Operating License No. NPF-77 for the Braidwood Station, Units 1 and 2, respectively;
- 2.
Amendment No. 209 to Renewed Facility Operating License No. NPF-37 and Amendment No. 209 to Renewed Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively;
- 3.
Amendment No. 227 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit No. 1;
- 4.
Amendment No. 262 to Renewed Facility Operating License No. DPR-19 and Amendment No. 255 to Renewed Facility Operating License No. DPR-25 for the Dresden Nuclear Power Station, Units 2 and 3, respectively;
- 5.
Amendment No. 329 to Renewed Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant;
- 6.
Amendment No. 239 to Renewed Facility Operating License No. NPF-11 and Amendment No. 225 to Renewed Facility Operating License No. NPF-18 for the LaSalle County Station, Units 1 and 2, respectively; and
- 7.
Amendment No. 275 to Renewed Facility Operating License No. DPR-29 and Amendment No. 270 to Renewed Facility Operating License No. DPR-30 for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively.
B. Hanson
.. 2 -
The amendments revise the technical specifications for each facility to eliminate second completion times based on Technical Specification Task Force (TSTF) traveler TSTF-439, Revision 2, "Eliminate Second Completion Times Limiting Time Frame from Discovery of Failure to Meet an LCO [Limiting Condition for Operation]" (ADAMS Accession No. ML051860296). In addition, the amendment for the James A. FitzPatrick Nuclear Power Plant also deletes an obsolete footnote in Technical Specification 3.8.1, "AC Sources - Operating."
A copy of the NRC staff's Safety Evaluations are also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Docket Nos. STN 50-456, STN 50-457,
Enclosures:
STN 50-454, STN 50-455, 50-461, 50-237, 50-249, 50-333, 50-373, 50-37 4, 50-254, and 50-265
- 1. Amendment No. 203 to NPF-72
- 2. Amendment No. 203 to NPF-77
- 3. Amendment No. 209 to NPF-37
- 4. Amendment No. 209 to NPF-66
- 5. Amendment No. 227 to NPF-62
- 6. Amendment No. 262 to DPR-19
- 7. Amendment No. 255 to DPR-25
- 8. Amendment No. 329 to DPR-59
- 9. Amendment No. 239 to NPF-11
- 10. Amendment No. 225 to NPF-18
- 11. Amendment No. 275 to DPR-29
- 12. Amendment No. 270 to DPR-30
- 13. Safety Evaluation cc: Listserv Blake Purnell, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 203 Renewed License No. NPF-72
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated November 1, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-72 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 203 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lisa M. Regner, Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: October 8, 2 O 1 9
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 203 Renewed License No. NPF-77
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated November 1, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-77 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 203 and the Environmental Protection Plan contained in Appendix B, both of which are attached to Renewed License No. NPF-72, dated January 27, 2016, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lisa M. Regner, Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: October 8, 2 O 1 9
ATTACHMENT TO LICENSE AMENDMENT NOS. 203 AND 203 RENEWED FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications (TSs ), with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License NPF-72 Page 3 License NPF-77 Page 3 TSs 1.3-3 1.3-6 1.3-7 3.6.6-1 3.8.1-1 3.8.1-3 3.8.9-2 License NPF-72 Page 3 License NPF-77 Page 3 TSs 1.3-3 1.3-6 1.3-7 3.6.6-1 3.8.1-1 3.8.1-3 3.8.9-2 (2)
Exelon Generation Company, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)
Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 203 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Renewed License No. NPF-72 Amendment 203 (2)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Exelon Generation Company, LLC, pursuant to the Act and 1 O CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
The renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 203 and the Environmental Protection Plan contained in Appendix B, both of which are attached to Renewed License No. NPF-72, dated January 27, 2016, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Renewed License No. NPF-77 Amendment 203
Completion Times Completion Times
1.3 DESCRIPTION
(continued)
EXAMPLES The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery... "
The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and associated AND Completion Time not B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> met.
Condition B has two Required Actions.
Each Required Action has its own separate Completion Time.
Each Completion Time is referenced to the time that Condition Bis entered.
The Required Actions of Condition Bare to be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. A total of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (not 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, the time allowed for reaching MODE 5 is the next 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> because the total time allowed for reaching MODE 5 is 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
If Condition Bis entered while in MODE 3, the time allowed for reaching MODE 5 is the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
BRAIDWOOD - UNITS 1 & 2 1.3 - 3 Amendment 203
1.3 Completion Times EXAMPLES (continued)
EXAMPLE 1.3-3 ACTIONS CONDITION A. One Function X train inoperable.
B. One Function Y train inoperable.
C. One Function X train inoperable.
AND One Function Y train inoperable.
BRAIDWOOD - UNITS 1 & 2 REQUIRED ACT ION A.l Restore Function X train to OPERABLE status.
B.l Restore Function Y train to OPERABLE status.
C.l Restore Function X train to OPERABLE status.
OR C.2 Restore Function Y train to OPERABLE status.
1.3 - 6 Completion Times 1.3 COMPLETION TIME 7 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Amendment 203
1.3 Completion Times EXAMPLES (continued)
Completion Times 1.3 When one Function X train and one Function Y train are inoperable, Condition A and Condition Bare concurrently applicable. The Completion Times for Condition A and Condition Bare tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).
If Required Action C.2 is completed within the specified Completion Time, Conditions Band Care exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A.
The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e.,
initial entry into Condition A).
It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCD.
- However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCD.
These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.
BRAIDWOOD - UNITS 1 & 2 1.3 - 7 Amendment 203
3.6 CONTAINMENT SYSTEMS Containment Spray and Cooling Systems 3.6.6 3.6.6 Containment Spray and Cooling Systems LCO 3.6.6 Two containment spray trains and two containment cooling trains shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One containment spray A.l Restore containment 7 days train inoperable.
spray train to OPERABLE status.
B.
Required Action and B.l Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A AND not met.
B.2 Be in MODE 5.
84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> C.
One or more C.1 Restore containment 7 days containment cooling cooling train(s) to trains inoperable.
OPERABLE status.
(continued)
BRAIDWOOD - UNITS 1 & 2 3.6.6 - 1 Amendment 203
3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating AC Sources-Operating 3.8.1 LCO 3.8.1 The following AC electrical sources shall be OPERABLE:
- a.
Two qualified circuits per bus between the offsite transmission network and the onsite Class lE AC Electrical Power Distribution System; and
- b.
Two Diesel Generators (DGs) capable of supplying the onsite Class lE AC Electrical Power Distribution System.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS
NOTE---------------------------------
LCO 3.0.4.b is not applicable to DGs.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more buses with A. l Perform SR 3.8.1.1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> one required qualified for the required circuit inoperable.
OPERABLE qualified AND circuits.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter AND A.2 Restore required 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> qualified circuit(s) to OPERABLE status.
(continued)
BRAIDWOOD - UNITS 1 & 2 3.8.1 - 1 Amendment 203
ACTIONS CONDITION B.
(continued)
C.
Required Action and associated Completion Time of Required Action B.l not met.
D.
One or more buses with two required qualified circuits inoperable.
E.
One DG inoperable and one or more buses with one required qualified circuit inoperable.
OR One DG inoperable and one bus with two required qualified circuits inoperable.
BRAIDWOOD - UNITS 1 & 2 REQUIRED ACTION B.5 Restore DG to OPERABLE status.
C.1 Restore DG to OPERABLE status.
0.1 Restore one required AC Sources-Operating 3.8.1 COMPLETION TIME 14 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 24 hours qualified circuit per bus to OPERABLE status.
NOTE-------------
Enter applicable Conditions and Required Actions of LCD 3.8.9, "Distribution Systems-Operating," when Condition Eis entered with no AC power source to a division.
E.1 Restore required qualified circuit(s) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to OPERABLE status.
OR E.2 Restore DG to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OPERABLE status.
(continued) 3.8.1 - 3 Amendment 203
ACTIONS CONDITION A.
One AC electrical A.1 power distribution subsystem inoperable.
B.
One AC instrument bus B.1 electrical power distribution subsystem inoperable.
C.
One DC electrical C.l power distribution subsystem inoperable.
D.
Required Action and 0.1 associated Completion Time of Condition A, AND B, or C not met.
0.2 BRAIDWOOD - UNITS 1 & 2 Distribution Systems-Operating 3.8.9 REQUIRED ACTION COMPLETION TIME Restore AC electrical 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> power distribution subsystem to OPERABLE status.
Restore AC instrument 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> bus electrical power distribution subsystem to OPERABLE status.
Restore DC electrical 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> power distribution subsystem to OPERABLE status.
Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued) 3.8.9 - 2 Amendment 203
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-454 BYRON STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 209 Renewed License No. NPF-37
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated November 1, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-37 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 209 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
)~i~t.-
Lisa M. Regner, Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: October 8, 2 o 1 9
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-455 BYRON STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 209 Renewed License No. NPF-66
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated November 1, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-66 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 209, and the Environmental Protection Plan contained in Appendix B, both of which were attached to Renewed License No. NPF-37, dated November 19, 2015, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
\\{~(_~fr.-
Lisa M. Regner, Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: October 8, 2 o 1 9
ATTACHMENT TO LICENSE AMENDMENT NOS. 209 AND 209 RENEWED FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-454 AND STN 50-455 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications (TSs), with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License NPF-37 Page 3 License NPF-66 Page 3 TSs 1.3-3 1.3-6 1.3-7 3.6.6-1 3.8.1-1 3.8.1-3 3.8.9-2 License NPF-37 Page 3 License NPF-66 Page 3 TSs 1.3-3 1.3-6 1.3-7 3.6.6-1 3.8.1-1 3.8.1-3 3.8.9-2 (2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3)
Pursuant to the Act and 1 O CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
The renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 1 O CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level (2)
The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent power) in accordance with the conditions specified herein.
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 209 and the Environmental Protection Plan contained in Appendix 8, both of which are attached hereto, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Deleted.
(4)
Deleted.
Renewed License No. NPF-37 Amendment No. 209 (2)
Pursuant to the Act and 1 O CFR Part 70, to receive; possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
The renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 1 O CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 209, and the Environmental Protection Plan contained in Appendix B, both of which were attached to Renewed License No. NPF-37, dated November 19, 2015, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Renewed License No. NPF-66 Amendment 209
Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued)
EXAMPLES The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery... "
The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.l Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and associated AND Completion Time not B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> met.
Condition B has two Required Actions.
Each Required Action has its own separate Completion Time.
Each Completion Time is referenced to the time that Condition Bis entered.
The Required Actions of Condition Bare to be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. A total of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (not 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />) is allowed for reaching MODE 5 from the time that Condition B was entered.
If MODE 3 is reached within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, the time allowed for reaching MODE 5 is the next 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> because the total time allowed for reaching MODE 5 is 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
If Condition Bis entered while in MODE 3, the time allowed for reaching MODE 5 is the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
BYRON - UNITS 1 & 2 1.3 - 3 Amendment 209
1.3 Completion Times EXAMPLES (continued)
EXAMPLE 1.3-3 ACTIONS CONDITION A. One Function X train inoperable.
B. One Function Y train inoperable.
C. One Function X train inoperable.
AND One Function Y train inoperable.
BYRON - UNITS 1 & 2 REQUIRED ACTION A.1 Restore Function X train to OPERABLE status.
B.1 Restore Function Y train to OPERABLE status.
C.1 Restore Function X train to OPERABLE status.
OR C.2 Restore Function Y train to OPERABLE status.
1.3 - 6 Completion Times 1.3 COMPLETION TIME 7 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Amendment 209
1.3 Completion Times EXAMPLES (continued)
Completion Times 1.3 When one Function X train and one Function Y train are inoperable, Condition A and Condition Bare concurrently applicable.
The Completion Times for Condition A and Condition Bare tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).
If Required Action C.2 is completed within the specified Completion Time, Conditions Band Care exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A.
The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e.,
initial entry into Condition A).
It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO.
- However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO.
These administrative controls shall ensure that the Completion Times for those conditions are not inappropriately extended.
BYRON - UNITS 1 & 2 1.3 - 7 Amendment 209
3.6 CONTAINMENT SYSTEMS Containment Spray and Cooling Systems 3.6.6 3.6.6 Containment Spray and Cooling Systems LCD 3.6.6 Two containment spray trains and two containment cooling trains shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One containment spray A.1 Restore containment 7 days train inoperable.
spray train to OPERABLE status.
B.
Required Action and B.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A AND not met.
B.2 Be in MODE 5.
84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> C.
One or more C.1 Restore containment 7 days containment cooling cooling train(s) to trains inoperable.
OPERABLE status.
(continued)
BYRON - UNITS 1 & 2 3.6.6 - 1 Amendment 209
3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating AC Sources-Operating 3.8.1 LCO 3.8.1 The following AC electrical sources shall be OPERABLE:
- a.
Two qualified circuits per bus between the offsite transmission network and the onsite Class lE AC Electrical Power Distribution System; and
- b.
Two Diesel Generators (DGs) capable of supplying the onsite Class lE AC Electrical Power Distribution System.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS
NOTE-------------------------------------
LCO 3.0.4.b is not applicable to DGs.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more buses with A. l Perform SR 3.8.1.1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> one required qualified circuit inoperable.
for the required OPERABLE qualified AND circuits.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter AND A.2 Restore required qualified circuit(s) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to OPERABLE status.
(continued)
BYRON - UNITS 1 & 2 3.8.1-1 Amendment 209
ACTIONS CONDITION B.
(continued)
C.
Required Action and associated Completion Time of Required Action B.l not met.
- 0.
One or more buses with two required qualified circuits inoperable.
E.
One DG inoperable and one or more buses with one required qualified circuit inoperable.
OR One DG inoperable and one bus with two required qualified circuits inoperable.
BYRON - UNITS 1 & 2 REQUIRED ACTION B.5 Restore DG to OPERABLE status.
C.1 Restore DG to OPERABLE status.
0.1 Restore one required AC Sources-Operating 3.8.1 COMPLETION TIME 14 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 24 hours qualified circuit per bus to OPERABLE status.
NOTE-------------
Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution Systems-Operating," when Condition Eis entered with no AC power source to a division.
E.1 Restore required 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> qualified circuit(s) to OPERABLE status.
OR E.2 Restore DG to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OPERABLE status.
(continued) 3.8.1 - 3 Amendment 209
ACTIONS CONDITION A.
One AC electrical A. l power distribution subsystem inoperable.
B.
One AC instrument bus B.l electrical power distribution subsystem inoperable.
C.
One DC electrical C.l power distribution subsystem inoperable.
D.
Required Action and D.l associated Completion Time of Condition A, AND B, or C not met.
D.2 BYRON - UNITS 1 & 2 Distribution Systems-Operating 3.8.9 REQUIRED ACTION COMPLETION TIME Restore AC electrical 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> power distribution subsystem to OPERABLE status.
Restore AC instrument 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> bus electrical power distribution subsystem to OPERABLE status.
Restore DC electrical 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> power distribution subsystem to OPERABLE status.
Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued) 3.8.9 - 2 Amendment 209
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 227 License No. NPF-62
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated November 1, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 227, are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l<~~~Pv-usa M. Regner, Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance:
October 8, 2 O 1 9
AITACHMENT TO LICENSE AMENDMENT NO. 227 FACILITY OPERATING LICENSE NO. NPF-62 CLINTON POWER STATION, UNIT NO. 1 DOCKET NO. 50-461 Replace the following pages of the Facility Operating License and Appendix A, Technical Specifications (TSs ), with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License NPF-62 Page 3 TSs 1.0-12 1.0-16 1.0-17 3.8-1 3.8-2 3.8-39 3.8-40 License NPF-62 Page 3 TSs 1.0-12 1.0-16 1.0-17 3.8-1 3.8-2 3.8-39 3.8-40 (4)
Exelon Generation Company, pursuant to the Act and to 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (6)
Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
Mechanical disassembly of the GE14i isotope test assemblies containing Cobalt-60 is not considered separation; and (7)
Exelon Generation Company, pursuant to the Act and 1 O CFR Parts 30, to intentionally produce, possess, receive, transfer, and use Cobalt-60.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level Exelon Generation Company is authorized to operate the facility at reactor core power levels not in excess of 3473 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 227, are hereby incorporated into this license.
Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Amendment No. 227
Completion Times
- 1. 3 1.3 Completion Times DESCRIPTION (continued)
CLINTON for each Condition starting from the discovery of the situation that required entry into the Condition, unless otherwise specified.
Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated.
The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition, unless otherwise specified.
However, when a subsequent division, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended.
To apply this Completion Time extension, two criteria must first be met.
The subsequent inoperability:
- a.
Must exist concurrent with the first inoperability; and
- b.
Must remain inoperable or not within limits after the first inoperability is resolved.
The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:
- a.
The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; or
- b.
The stated Completion Time as measured from discovery of the subsequent inoperability.
The above Completion Time extension does not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry.
These exceptions are stated in individual Specifications.
The above Completion Time extension does not apply to a Completion Time with a modified "time zero."
This modified "time zero" may be expressed as a repetitive time (i.e.,
"once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery.
II (continued) 1.0-12 Amendment No. 227
1.3 Completion Times EXAMPLES (continued)
CLINTON EXAMPLE 1.3-3 ACTIONS CONDITION A.
One Function X subsystem inoperable.
B.
One Function y subsystem inoperable.
C. One Function X subsystem inoperable.
AND One Function y subsystem inoperable.
REQUIRED ACTION A.1 Restore Function X subsystem to OPERABLE status.
B.1 Restore Function y subsystem to OPERABLE status.
C.1 Restore Function X subsystem to OPERABLE status.
OR C.2 Restore Function y subsystem to OPERABLE status.
1.0-16 Completion Times
- 1. 3 COMPLETION TIME 7 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)
Amendment No. 227
Completion Times 1.3 1.3 Completion Times EXAMPLES CLINTON EXAMPLE 1.3-3 (continued)
When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition Bare concurrently applicable.
The Completion Times for Condition A and Condition Bare tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered.
A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).
If Required Action C.2 is completed within the specified Completion Time, Conditions Band Care exited.
If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A.
The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).
It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO.
- However, doing so would be inconsistent with the basis of the Completion Times.
Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO.
These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.
(continued) 1.0-17 Amendment No. 227
AC Sources~Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources~Operating LCO
3.8.1 APPLICABILITY
ACTIONS The following AC electrical power sour~es shall be OPERABLE:
- a.
Two qualified circuits between the offsite transmission network and the onsite Class lE AC Electric Power Distribution System; and
- b.
Three diesel generators (DGs).
MODES 1, 2, and 3.
NOTE----------------------------
Division 3 AC electrical power sources are not required to be OPERABLE when High Pressure Core Spray System is inoperable.
NOTE-------------------------------------
LCO 3.0.4.b is not applicable to DGs.
CONDITION A.
One offsite circuit inoperable.
CLINTON A.1 AND A.2 REQUIRED ACTION Perform SR 3.8.1.1 for OPERABLE offsite circuit.
Restore offsite circuit to OPERABLE status.
3.8-1 COMPLETION TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)
Amendment No. 227
ACTIONS (continued)
CONDITION B.
One required DG inoperable.
CLINTON B. l AND B.2 AND B.3.1 OR B.3.2 AND B. 4 AC Sources~Operating
- 3. 8. 1 REQUIRED ACTION Perform SR 3.8.1.1 for OPERABLE offsite circuit(s).
Declare required feature(s), supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable.
Determine OPERABLE DG(s) are not inoperable due to common cause failure.
Perform SR 3.8.1.2 for OPERABLE DG(s).
Restore required DG to OPERABLE status.
3.8-2 COMPLETION TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of Condition B concurrent with inoperability of redundant required feature(s) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from discovery of an inoperable Division 3 DG AND 14 days (continued)
Amendment No. 227
Distribution Systems-Operating
- 3. 8. 9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems~Operating LCO 3.8.9 Division 1, 2, and 3 AC, Division 1, 2, 3, and 4 DC, and Division 1, 2, 3, and 4 uninterruptible AC bus electrical power distribution subsystems shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
NOTE----------------------------
Division 3 and 4 electrical power distribution subsystems are not required to be OPERABLE when High Pressure Core Spray System is inoperable.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more Division 1 A.1 Restore Division 1 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or 2 AC electrical and 2 AC electrical power distribution power distribution subsystems inoperable.
subsystems to OPERABLE status.
B.
One or more Division 1 B.1 Restore Division 1 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or 2 uninterruptible and 2 uninterruptible AC bus distribution AC bus distribution subsystems inoperable.
subsystems to OPERABLE status.
(continued)
CLINTON 3.8-39 Amendment No. 227
Distribution Systems~Operating 3.8.9 ACTIONS (continued)
CONDITION C.
One or more Division 1 C.1 or 2 DC electrical power distribution subsystems inoperable.
REQUIRED ACTION Restore Division 1 and 2 DC electrical power distribution subsystems to OPERABLE status.
D.
Required Action and associated Completion Time of Condition A, B, or C not met.
NOTE------------
LCO 3.0.4.a is not applicable when entering MODE 3.
D.1 E.
One or more Division 3 E.1 or 4 AC, DC, or uninterruptible AC bus electrical power distribution subsystems inoperable.
F.
Two or more divisions F.1 with inoperable distribution subsystems that result in a loss of function.
CLINTON Be in MODE 3.
Declare High Pressure Core Spray System inoperable.
Enter LCO 3.0.3.
3.8-40 COMPLETION TIME 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 12 hours Immediately Immediately Amendment No. 227
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 262 Renewed License No. DPR-19
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated November 1, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-19 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 262, are hereby incorporated into this renewed operating license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lisa M. Regner, Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:
October 8, 201 9
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 255 Renewed License No. DPR-25
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated November 1, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8. of Renewed Facility Operating License No. DPR-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 255, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l<~~h' Lisa M. Regner, Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: October 8, 201 9
ATTACHMENT TO LICENSE AMENDMENT NOS. 262 AND 255 RENEWED FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-237 AND 50-249 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications (TSs), with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License DPR-19 Page 3 License DPR-25 Page 4 TSs 1.3-3 1.3-6 1.3-7 3.8.1-2 3.8.1-3 3.8.7-1 3.8.7-2 License DPR-19 Page 3 License DPR-25 Page 4 TSs 1.3-3 1.3-6 1.3-7 3.8.1-2 3.8.1-3 3.8.7-1 3.8.7-2 (2)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear materials as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2957 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 262, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Operation in the coastdown mode is permitted to 40% power.
Renewed License No. DPR-19 Amendment No. 262
- f.
Surveillance Requirement 4.9.A.10 - Diesel Storage Tank Cleaning (Unit 3 and Unit 2/3 only)
Each of the above Surveillance Requirements shall be successfully demonstrated prior to entering into MODE 2 on the first plant startup following the fourteenth refueling outage (D3R14).
- 3.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
A.
Maximum Power Level B.
The licensee is authorized to operate the facility at steady state power levels not in excess of 2957 megawatts (thermal), except that the licensee shall not operate the facility at power levels in excess of five (5) megawatts (thermal), until satisfactory completion of modifications and final testing of the station output transformer, the auto-depressurization interlock, and the feedwater system, as described in the licensee's telegrams; dated February 26, 1971, have been verified in writing by the Commission.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 255, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
Reports The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.
D.
Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E.
Restrictions Operation in the coastdown mode is permitted to 40% power.
Renewed License No. DPR-25 Amendment No. 255
Completion Times
- 1. 3 1.3 Completion Times DESCRIPTION (continued)
EXAMPLES Dresden 2 and 3 subsystem, component or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry.
These exceptions are stated in individual Specifications.
The above Completion Time extension does not apply to a Completion Time with a modified "time zero."
This modified "time zero" may be expressed as a repetitive time (i.e.,
"once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery... "
The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
EXAMPLE 1.3-1 ACTIONS CONDITION B.
Required Action and associated Completion Time not met.
REQUIRED ACTION B.l Be in MODE 3.
B.2 Be in MODE 4.
COMPLETION TIME 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Condition B has two Required Actions.
Each Required Action has its own separate Completion Time.
Each Completion Time is referenced to the time that Condition Bis entered.
The Required Actions of Condition Bare to be in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
A total of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (not 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) is allowed for reaching MODE 4 from (continued)
- 1. 3-3 Amendment No. 262/255
1.3 Completion Times EXAMPLES (continued)
Dresden 2 and 3 EXAMPLE 1.3-3 ACTIONS CONDITION A.
One Function X subsystem inoperable.
B.
One Function y subsystem inoperable.
C.
One Function X subsystem inoperable.
AND One Function y subsystem inoperable.
REQUIRED ACTION A.1 Restore Function X subsystem to OPERABLE status.
B. 1 Restore Function y subsystem to OPERABLE status.
C.l Restore Function X subsystem to OPERABLE status.
OR C.2 Restore Function y subsystem to OPERABLE status.
Completion Times
- 1. 3 COMPLETION TIME 7 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)
- 1. 3-6 Amendment No. 262/255
Completion Times
- 1. 3 1.3 Completion Times EXAMPLES Dresden 2 and 3 EXAMPLE 1.3-3 (continued)
When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition Bare concurrently applicable.
The Completion Times for Condition A and Condition Bare tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered.
A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).
If Required Action C.2 is completed within the specified Completion Time, Conditions Band Care exited.
If the Completion Time for Required Action A.l has not expired, operation may continue in accordance with Condition A.
The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).
It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO.
- However, doing so would be inconsistent with the basis of the Completion Times.
Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO.
These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.
(continued)
- 1. 3-7 Amendment No. 262/255
ACTIONS AC Sources-Operating 3.8.1 C
- NOTE- - - - - - - - - - - - - - - - - - -- - -- - - - - - - - - - - - - - -
LCO 3.0.4.b is not applicable to the unit and common DGs, but is applicable to the opposite unit DG.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One required offsite A.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> circuit inoperable.
for OPERABLE required offsite circuit.
AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter AND A.2 Declare required 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from feature(s) with no discovery of no offs ite power offsite power to available inoperable one division when the redundant concurrent with required feature(s) inoperability of are inoperable.
redundant required feature(s)
AND A.3 Restore required 7 days offsite circuit to OPERABLE status.
(continued)
Dresden 2 and 3 3.8.1-2 Amendment No. 262/255
ACTIONS CONDITION B.
One required DG B. 1 inoperable.
.81::ill B.2 AND B.3.1 OR B.3.2 AND B.4 Dresden 2 and 3 AC Sources-Operating 3.8.1 REQUIRED ACTION COMPLETION TIME Perform SR 3.8.1.1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for OPERABLE required offsite circuit(s).
AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter Declare required 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from feature ( s), supported discovery of by the inoperable DG, Condition B inoperable when the concurrent with redundant required inoperability of feature(s) are redundant inoperable.
required feature(s)
Determine OPERABLE 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DG(s) are not inoperable due to common cause failure.
Perform SR 3.8.1.2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for OPERABLE DG(s).
Restore required DG 7 days to OPERABLE status.
(continued) 3.8.1-3 Amendment No. 262/255
Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO
3.8.7 APPLICABILITY
ACTIONS The following electrical power distribution subsystems shall be OPERABLE:
- a.
Division 1 and Division 2 AC and DC electrical power distribution subsystems; and
- b.
The portions of the opposite unit's Division 2 AC and DC electrical power distribution subsystem necessary to support equipment required to be OPERABLE by LCO 3.6.4.3, "Standby Gas Treatment (SGT) System,"
LCO 3.7.4, "Control Room Emergency Ventilation (CREV)
System" (Unit 3 only), LCO 3.7.5, "Control Room Emergency Ventilation Air Conditioning (AC) System" (Unit 3 only), and LCO 3.8.1, "AC Sources-Operating."
MODES l, 2, and 3.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more AC A.l electrical power distribution subsystems inoperable.
Dresden 2 and 3 Restore AC electrical 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> power distribution subsystems to OPERABLE status.
(continued) 3.8.7-1 Amendment No. 262/255
ACTIONS CONDITION Distribution Systems-Operating 3.8.7 REQUIRED ACTION COMPLETION TIME B.
One or more DC B.l Restore DC electrical 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> power distribution C.
electrical power distribution subsystems inoperable.
One or more required opposite unit Division 2 AC or DC electrical power distribution subsystems inoperable.
D.
Required Action and associated Completion Time of Condition A, B, or C not met.
subsystems to OPERABLE status.
-- - - - - - - - - - - -NOTE - - - - - - - - - - - -
Enter applicable Conditions and Required Actions of LCO 3.8.1 when Condition C results in the inoperability of a required offsite circuit.
C.l Restore required opposite unit Division 2 AC and DC electrical power distribution subsystems to OPERABLE status.
- - - - - - - - - - - -NOTE- - - - - - - - - - - - -
LCO 3.0.4.a is not applicable when entering MODE 3.
D.l Be in MODE 3.
E.
Two or more electrical E.l power distribution subsystems inoperable Enter LCO 3.0.3.
that, in combination, result in a loss of function.
7 days 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Immediately Dresden 2 and 3 3.8.7-2 Amendment No. 262/255
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON FITZPATRICK, LLC AND EXELON GENERATION COMPANY, LLC DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 329 Renewed License No. DPR-59
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated November 1, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-59 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 329, are hereby incorporated in the renewed operating license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Lisa M. Regner, Acting Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:
October 8, 2 O 1 9
AITACHMENT TO LICENSE AMENDMENT NO. 329 RENEWED FACILITY OPERATING LICENSE NO. DPR-59 JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License DPR-59 Page 3 TSs 1.3-2 1.3-6 1.3-7 3.8.1-2 3.8.1-3 3.8.7-1 License DPR-59 Page 3 TSs 1.3-2 1.3-6 1.3-7 3.8.1-2 3.8.1-3 3.8.7-1 (4)
Exelon Generation Company pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools.
(5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level Exelon Generation Company is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).
(2)
Technical Specifications (3)
The Technical Specifications contained in Appendix A, as revised through Amendment No. 329, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
Fire Protection Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement No. 1 dated February 1, 1973; the SER Supplement No. 2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978), 80 (dated May 22, 1984), 134 (dated July 19, 1989),
135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993), 190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994), and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, Amendment 329 Renewed License No. DPR-59
1.3 Completion Times DESCRIPTION (continued}
JAFNPP Completion Times 1.3 However, when a subseguent division, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s} may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:
- a. Must exist concurrent with the first inoperability;
~nd
- b. Must remain inoperable or not within limits after the first inoperability is resolved.
The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:
- a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; or
- b. The stated Completion Time as measured from discovery of the subsequent inoperability.
The above Completion lime extension does not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component or variable expressed in the Condition}
and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.
The above Completion lime extension does not apply to a Completion Time with a modified *time zero.* This modified
- time zero* may be expressed as a repetitive time (i.e.,
- once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,* where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry} or as a time modified by the phrase
- from discovery...
- 1.3-2 (continued}
Amendment 329
1.3 Completion Times EXAMPLES (continued)
JAFNPP EXAMPLE 1.3-3 ACTIONS CONDITION A. One Function X subsystem inoperable.
B. One Function Y subsystem inoperable.
C. One Function X subsystem inoperable.
AND One Function y subsystem inoperable.
REQUIRED ACTION A.1 Restore FunctionX subsystem to OPERABLE status.
B.1 Restore FunctionY subsystem to OPERABLE status.
C.1 Restore Function X subsystem to OPERABLE status.
OR C.2 Restore FunctionY subsystem to OPERABLE status.
1.3-6 Completion Times 1.3 COMPLETION TIME 7 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 12 hours 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)
Amendment 329
1.3 Completion Times EXAMPLES JAFNPP EXAMPLE 1.3-3 (continued)
Completion Times 1.3 When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).
If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A.
The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).
It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.
(continued) 1.3-7 Amendment 329
ACTIONS CONDITION A.
(continued)
A.3 B.
One EOG subsystem B.1 inoperable AND B.2 AND B.3.1 OR B.3.2 AND JAFNPP REQUIRED ACTION Restore offsite circuit to OPERABLE status.
Perform SR 3.8.1.1 for OPERABLE offsite circuit(s).
Declare required feature(s), supported by the inoperable EOG subsystem, inoperable when the redundant required feature(s) are inoperable.
Determine OPERABLE EOG subsystem is not inoperable due to common cause failure.
Perform SR 3.8.1.2 for OPERABLE EOG subsystem.
3.8.1-2 AC Sources - Operating 3.8.1 COMPLETION TIME 7 days 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of Condition B concurrent with inoperability of redundant required feature(s) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours (continued)
Amendment 329
ACTIONS CONDITION B.
(continued)
C.
Two offsite circuits inoperable.
D.
One offsite circuit inoperable.
AND One EOG subsystem inoperable JAFNPP AC Sources - Operating 3.8.1 REQUIRED ACTION COMPLETION TIME B.4 Restore EOG subsystem 14days to OPERABLE status.
C.1 Declare required 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from feature(s) inoperable discovery of when the redundant Condition C required feature(s) are concurrent with inoperable.
inoperability of redundant required feature(s)
AND C.2 Restore one offsite 7 days circuit to OPERABLE status.
NOTE-------
Enter applicable Conditions and Required Actions of LCO 3.8. 7, "Distribution Systems ;..
Operating," when Condition D is entered with no AC power source to any division.
D.1 Restore Offsite circuit to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OPERABLE status.
OR (continued) 3.8.1-3 Amendment 329
3.8 ELECTRICAL POWER SYSTEMS Distribution Systems - Operating 3.8.7 3.8. 7 Distribution Systems - Operating LCO 3.8. 7 The Division 1 and Division 2 AC and 125 VDC electrical power distribution subsystems shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more AC A.1 Restore AC electrical 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> electrical power power distribution distribution subsystems to subsystems OPERABLE status.
B.
One 125 VDC 8.1 Restore 125 voe 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> electrical power electrical power distribution distribution subsystem subsystem to OPERABLE inoperable.
status.
C.
Required Action C.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and associated Completion Time AND of Condition A or B not met.
C.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)
JAFNPP 3.8.7-1 Amendment 329
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 239 Renewed License No. NPF-11
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated November 1, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.{2) of Renewed Facility Operating License No. NPF-11 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 239, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lisa M. Regner, ranch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:
October 8, 201 9
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 225 Renewed License No. NPF-18
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated November 1, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-18 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 225, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 0
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION I<~~~
Lisa M. Regner, Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: October 8, 201 9
A TI ACHMENT TO LICENSE AMENDMENT NOS. 239 AND 225 RENEWED FACILITY OPERATING LICENSE NOS. NPF-11 AND NPF-18 LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374
. Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications (TSs), with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License NPF-11 Page 3 License NPF-18 Page 3 TSs 1.3-3 1.3-6 1.3-7 3.8.1-2 3.8.1-3 3.8.1-4 3.8.7-1 3.8.7-2 License NPF-11 Page 3 License NPF-18 Page 3 TSs 1.3-3 1.3-6 1.3-7 3.8.1-2 3.8.1-3 3.8.1-4 3.8.7-1 3.8.7-2
Am. 146 01/12/01 Am. 202 07/21/11 Am. 198 09/16/10 Am. 239 10/08/19 Am. 194 08/28/09 Am. 194 08/28/09 Am. 194 08/28/09 Renewed License No. NPF-11 (3)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
(5)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station, Units 1 and 2, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 1 O CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
(2)
(3)
(4)
(5)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3546 megawatts thermal).
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 239, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
DELETED DELETED DELETED Amendment No. 239
Am. 189 07/21/11 Am. 185 09/16/10 Am. 225 10/08/19 Renewed License No. NPF-18 (2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station, Units 1 and 2, and such Class Band Class Clow-level radioactive waste as may be produced by the operation of Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 1 O CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
(2)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3546 megawatts thermal). Items in shall be completed as specified. Attachment 1 is hereby incorporated into this license.
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 225, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Amendment No. 225
Completion Times
- 1. 3 1.3 Completion Times DESCRIPTION (continued)
EXAMPLES LaSalle 1 and 2 Condition) and separate tracking of Completion Times based on this re-entry.
These exceptions are stated in individual Specifications.
The above Completion Time extension does not apply to a Completion Time with a modified "time zero."
This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery... "
The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
EXAMPLE 1.3-1 ACTIONS CONDITION B.
Required Action and associated Completion Time not met.
REQUIRED ACTION B.1 Be in MODE 3.
B.2 Be in MODE 4.
COMPLETION TIME 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Condition B has two Required Actions.
Each Required Action has its own separate Completion Time.
Each Completion Time is referenced to the time that Condition Bis entered.
The Required Actions of Condition Bare to be in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
A total of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (not 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) is allowed for reaching MODE 4 from the time that Condition B was entered.
If MODE 3 is reached (continued)
- 1. 3-3 Amendment No. 239/225
1.3 Completion Times EXAMPLES (continued)
LaSalle 1 and 2 EXAMPLE 1.3-3 ACTIONS CONDITION A.
One Function X subsystem inoperable.
B.
One Function y subsystem inoperable.
C.
One Function X subsystem inoperable.
AND One Function y subsystem inoperable.
REQUIRED ACTION A.l Restore Function X subsystem to OPERABLE status.
B.l Restore Function y subsystem to OPERABLE status.
C.l Restore Function X subsystem to OPERABLE status.
1IB.
C.2 Restore Function y subsystem to OPERABLE status.
- 1. 3-6 Completion Times
- 1. 3 COMPLETION TIME 7 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)
Amendment No. 239/225
Completion Times
- 1. 3 1.3 Completion Times EXAMPLES LaSalle 1 and 2 EXAMPLE 1.3-3 (continued)
When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition Bare concurrently applicable.
The Completion Times for Condition A and Condition Bare tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered.
A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).
If Required Action C.2 is completed within the specified Completion Time, Conditions Band Care exited.
If the Completion Time for Required Action A.l has not expired, operation may continue in accordance with Condition A.
The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).
It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO.
- However, doing so would be inconsistent with the basis of the Completion Times.
Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO.
These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.
(continued)
- 1. 3-7 Amendment No. 239/225
ACTIONS AC Sources-Operating 3.8.1
- - - - - - - -- - - - - - -- - - - - -- - - - - - - - - -- - -- - - -NOTE - - - -- -- - - - - - - - - - -- - -- - -- - - - - - - - - - - -
LCO 3.0.4.b is not applicable to DGs.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One required offsite A.l Perform SR 3.8.1.1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> circuit inoperable.
for OPERABLE required off site circuit.
AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter AND A.2 Declare required 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from feature(s) with no discovery of no offsi te power offs ite power available inoperable to one division when the redundant concurrent with required feature(s) inoperability are inoperable.
of redundant required feature(s)
AND A.3 Restore required 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> offsite circuit to OPERABLE status.
(continued)
LaSalle 1 and 2 3.8.1-2 Amendment No. 239/225
ACTIONS CONDITION B.
One required Division B.1 1, or 2 DG inoperable.
Required opposite unit Division 2 DG inoperable.
LaSalle 1 and 2 B.2 B. 3.1 B.3.2 B.4 AC Sources-Operating 3.8.1 REQUIRED ACTION COMPLETION TIME Perform SR 3.8.1.1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for OPERABLE required offsite circuit(s).
AND Declare required feature( s), supported by the inoperable DG(s), inoperable when the redundant required feature(s) are inoperable.
Determine OPERABLE DG(s) are not inoperable due to common cause failure.
Perform SR 3.8.1.2 for OPERABLE DG(s).
Restore required DG(s) to OPERABLE status.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of Condition B concurrent with inoperability of redundant required feature(s) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours 14 days (continued) 3.8.1-3 Amendment No. 239/225
ACTIONS CONDITION C.
NOTE---------
C.l
- 1. Not applicable to the Division 2 DG and the opposite unit Division 2 DG during installation of Division 2 CSCS isolation valves during a single AND Unit 1 Refueling Outage completed C.2 prior to July 1, 2024, and during a single Unit 2 Refueling Outage completed prior to July 1, 2023, while the outage unit is in MODE 4,5, or defueled.
AND Required Division 3 DG inoperable.
OR One required Division C. 3.1 l, 2, or 3 DG C.3.2 inoperable and the required opposite unit Division 2 DG AN.Q.
C.4 LaSalle 1 and 2 AC Sources-Operating 3.8.l REQUIRED ACTION COMPLETION TIME Perform SR 3.8.1.1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for OPERABLE required offsite circuit(s).
AND Declare required feature(s), supported by the inoperable DG(s), inoperable when the redundant required feature(s) are inoperable.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of Condition C concurrent with i noperabi l i ty of redundant required feature(s)
Determine OPERABLE 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DG(s) are not inoperable due to common cause failure.
Perform SR 3.8.1.2 for OPERABLE DG(s).
Restore required DG(s) to OPERABLE status.
3.8.1-4 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 72 hours (continued)
Amendment No. 239/225
Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO
3.8.7 APPLICABILITY
ACTIONS The following electrical power distribution subsystems shall be OPERABLE:
- a.
Division 1 and Division 2 AC and 125 V DC distribution subsystems;
- b.
Division 3 AC and 125 V DC distribution subsystems;
- c.
Division 1 250 V DC distribution subsystem; and
- d.
The portions of the opposite unit's Division 2 AC and 125 V DC electrical power distribution subsystems capable of supporting the equipment required to be OPERABLE by LCO 3.6.4.3, "Standby Gas Treatment (SGT)
System," LCO 3.7.4, "Control Room Area Filtration (CRAF)
System," LCO 3.7.5, "Control Room Area Ventilation Air Conditioning (AC) System," and LCO 3.8.1, "AC Sources-Operating."
MODES 1, 2, and 3.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or both Division 1 A.l and 2 AC electrical power distribution subsystems inoperable.
LaSalle 1 and 2 Restore Division 1 and 2 AC electrical power distribution subsystems to OPERABLE status.
3.8.7-1 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (continued)
Amendment No. 239/225
ACTIONS CONDITION Distribution Systems-Operating 3.8.7 REQUIRED ACTION COMPLETION TIME B.
One or both Division 1 B.1 and 2 125 V DC Restore Division 1 and 2 125 V DC electrical power distribution subsystem(s) to OPERABLE status.
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> electrical power distribution subsystems inoperable.
C.
Required Action and C.l Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A or B not met.
D.
One or more required opposite unit Division 2 AC or DC electrical power distribution subsystems inoperable.
E.
Required Action and associated Completion Time of Condition D not met.
LaSalle 1 and 2
- - - - - - - - - - - - -NOTE- - - - - - - -- - - -
Enter applicable Conditions and Required Actions of LCO 3.8.1 when Condition C results in the inoperability of a required offsite circuit.
D.1 E. 1 E.2 Restore required opposite unit Division 2 AC and DC electrical power distribution subsystem(s).
Be in MODE 3.
Be in MODE 4.
7 days 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours (continued) 3.8.7-2 Amendment No. 239/225
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 275 Renewed License No. DPR-29
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated November 1, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
- 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 1
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8. of Renewed Facility Operating License No. DPR-29 is hereby amended to read as follows:
- 8.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 275, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lisa M. Regner, Acting Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:
October 8, 2 O 1 9
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERA TING LICENSE Amendment No. 270 Renewed License No. DPR-30
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated November 1, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
- 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8. of Renewed Facility Operating License No. DPR-30 is hereby amended to read as follows:
B.
Technical Specifications Tt,e Technical Specifications contained in Appendix A, as revised through Amendment No. 270, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lisa M. Regner, Acting Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:
October 8, 2 O 1 9
ATTACHMENT TO LICENSE AMENDMENT NOS. 275 AND 270 RENEWED FACILITY OPERATING LICENSES NOS. DPR-29 AND DPR-30 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications {TSs), with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License DPR-29 Page 4 License DPR-30 Page 4 TSs 1.3-3 1.3-6 1.3-7 3.8.1-2 3.8.1-3 3.8.7-1 3.8.7-2 License DPR-29 Page4 License DPR-30 Page 4 TSs 1.3-3 1.3-6 1.3-7 3.8.1-2 3.8.1-3 3.8.7-1 3.8.7-2 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 275, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
The licensee shall maintain the commitments made in response to the D.
March 14, 1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the N RC staff for review and approval prior to implementation of the change.
Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 1 O CFR 50.54(p). The combined sets of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.
Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 1 O CFR 50.90 and 10 CFR 50.54(p).
The Exelon Generation Company CSP was approved by License Amendment No. 249 as modified by License Amendment No. 259.
F.
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979 with supplements dated November 5, 1980, and 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-29 Amendment No. 275 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 270, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
The license shall maintain the commitments made in response to the D.
March 14, 1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval; pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Un reviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.
Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP),
including changes made pursuant to the authority of 1 O CFR 50.90 and 10 CFR 50.54(p). The Exelon Generation Company CSP was approved by License Amendment No. 244 and modified by License Amendment No. 254.
F.
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979 with supplements dated 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-30 Amendment No. 270
Completion Times
- 1. 3 1.3 Completion Times DESCRIPTION (continued)
EXAMPLES separate re-entry into the Condition (for each division, subsystem, component or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry.
These exceptions are stated in individual Specifications.
The above Completion Time extension does not apply to a Completion Time with a modified "time zero."
This modified "time zero" may be expressed as a repetitive time (i.e.,
"once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery... "
The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
EXAMPLE 1.3-1 ACTIONS CONDITION B.
Required Action and associated Completion Time not met.
REQUIRED ACTION B.l Be in MODE 3.
B.2 Be in MODE 4.
COMPLETION TIME 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Condition B has two Required Actions.
Each Required Action has its own separate Completion Time.
Each Completion Time is referenced to the time that Condition Bis entered.
The Required Actions of Condition Bare to be in MODE 3 within 12* hours AND in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
A total of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (not 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) is allowed for reaching MODE 4 from (continued)
Quad Cities 1 and 2
- 1. 3-3 Amendment No. 275/270
1.3 Completion Times EXAMPLES (continued)
EXAMPLE 1.3-3 ACTIONS CONDITION A.
One Function X subsystem inoperable.
B. One Function y subsystem inoperable.
C.
One Function X subsystem inoperable.
AND One Function y subsystem inoperable.
Quad Cities 1 and 2 REQUIRED ACTION A.l Restore Function X subsystem to OPERABLE status.
B.1 Restore Function y subsystem to OPERABLE status.
C.l Restore Function X subsystem to OPERABLE status.
OR C.2 Restore Function y subsystem to OPERABLE status.
Completion Times
- 1. 3 COMPLETION TIME 7 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)
- 1. 3-6 Amendment No. 275/270
Completion Times
- 1. 3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)
When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition Bare concurrently applicable.
The Completion Times for Condition A and Condition Bare tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered.
A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).
If Required Action C.2 is completed within the specified Completion Time, Conditions Band Care exited.
If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A.
The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).
It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO.
- However, doing so would be inconsistent with the basis of the Completion Times.
Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO.
These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.
(continued)
Quad Cities 1 and 2
- 1. 3-7 Amendment No. 275/270
ACTIONS AC Sources-Operating 3.8.1
- - - - - - - - - - - - - - - -- - - - - - - - - - - - - - -- - - - - -NOTE- - - - - - - - - - - - - - - - - - - - -- - - - - - -- - - - - - - - -
LCO 3.0.4.b is not applicable to the unit and common DGs, but is applicable to the opposite unit DG.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One required offsite A.l Perform SR 3.8.1.1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> circuit inoperable.
for OPERABLE required offsite circuit.
AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter AND A.2 Declare required 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from feature(s) with no discovery of no offsite power offsite power to available inoperable one division when the redundant concurrent with required feature(s) i noperabi 1 i ty of a re inoperable.
redundant required feature(s)
AND A.3 Restore required 7 days offsite circuit to OPERABLE status.
(continued)
Quad Cities 1 and 2 3.8.1-2 Amendment No. 275/270
ACTIONS CONDITION B.
One required DG B. 1 inoperable.
AND B.2 AND B. 3.1 OR B.3.2 AND B.4 Quad Cities 1 and 2 AC Sources-Operating 3.8.1 REQUIRED ACTION COMPLETION TIME Perform SR 3.8.1.1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for OPERABLE required offsite circuit(s).
AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter Declare required 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from feature(s), supported discovery of by the inoperable DG, Condition B inoperable when the concurrent with redundant required inoperability of feature(s) are redundant inoperable.
required feature(s)
Determine OPERABLE 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DG(s) are not inoperable due to common cause failure.
Perform SR 3.8.1.2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for OPERABLE DG(s).
Restore required DG 7 days to OPERABLE status.
(continued) 3.8.1-3 Amendment No. 275/270
Distribution Systems-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO
3.8.7 APPLICABILITY
ACTIONS The following electrical power distribution subsystems shall be OPERABLE:
- a.
Division 1 and Division 2 AC and DC electrical power distribution subsystems; and
- b.
The portions of the opposite unit's AC and DC electrical power distribution subsystems necessary to support equipment required to be OPERABLE by LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," LCO 3. 7.4, "Control Room Emergency Ventilation (CREV) System" (Unit 2 only), LCO 3.7.5, "Control Room Emergency Ventilation Air Conditioning (AC) System" (Unit 2 only),
and LCO 3. 8.1, "AC Sources-Operating."
MODES l, 2, and 3.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more AC A.l electrical power distribution subsystems inoperable.
Quad Cities 1 and 2 Restore AC electrical 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> power distribution subsystems to OPERABLE status.
(continued) 3.8.7-1 Amendment No. 275/270
Distribution Systems-Operating 3.8.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.
One or more DC B. 1 electrical power distribution Restore DC electrical 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> power distribution subsystems inoperable.
C.
One or more required opposite unit AC or DC electrical power distribution subsystems to OPERABLE status.
- - - - - - - - - -- - -NOTE- - - - - - - - - - - -
Enter applicable Condition and Required Actions of LCO 3.8.1 when Condition C subsystems inoperable.
results in the inoperability of a required offsite circuit.
C.l Restore required opposite unit AC and DC electrical power distribution subsystems to OPERABLE status.
D.
Required Action and associated Completion Time of Condition A, B, or C not met.
-- - - - -- -- - - - - -NOTE- - - - - - - - - - -
LCO 3.0.4.a is not applicable when entering MODE 3.
0.1 E.
Two or more electrical E.1 power distribution subsystems inoperable that, in combination, result in a loss of function.
Be in MODE 3.
Enter LCO 3.0.3.
7 days 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Immediately Quad Cities 1 and 2 3.8.7-2 Amendment No. 275/270
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 203 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-72, AMENDMENT NO. 203 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-77, AMENDMENT NO. 209 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-37, AMENDMENT NO. 209 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-66 1 AMENDMENT NO. 227 TO FACILITY OPERATING LICENSE NO. NPF-62, AMENDMENT NO. 262 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-19, AMENDMENT NO. 255 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-25, AMENDMENT NO. 329 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-59, AMENDMENT NO. 239 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-11, AMENDMENT NO. 225 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-18, AMENDMENT NO. 275 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29, AND AMENDMENT NO. 270 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30.
EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION, UNITS 1 AND 2 BYRON STATION, UNIT NOS. 1 AND 2 CLINTON POWER STATION, UNIT NO. 1 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 JAMES A. FITZPATRICK NUCLEAR POWER PLANT LASALLE COUNTY STATION, UNITS 1 AND 2 3 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-461, 50-237, 50-249, 50-333, 50-373, 50-374, 50-254, AND 50-265
1.0 INTRODUCTION
By application dated November 1, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML183058401), Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request for Braidwood Station, Units 1 and 2 (Braidwood); Byron Station, Unit Nos. 1 and 2 (Byron); Clinton Power Station, Unit No. 1 (Clinton); Dresden Nuclear Power Station, Units 2 and 3 (Dresden); James A FitzPatrick Nuclear Power Plant (FitzPatrick); LaSalle County Station, Units 1 and 2 (LaSalle); and Quad Cities Nuclear Power Station, Units 1 and 2 (Quad Cities) (the facilities). The amendments would revise the technical specifications (TSs) for each facility to eliminate second completion times based on Technical Specification Task Force (TSTF) traveler TSTF-439, Revision 2, "Eliminate Second Completion Times Limiting Time Frame from Discovery of Failure to Meet an LCO [Limiting Condition for Operation]" (ADAMS Accession No. ML051860296). In addition, the proposed amendment for FitzPatrick would also delete an obsolete footnote in TS 3.8.1, "AC
[Alternating-Current] Sources - Operating."
2.0
2.1 REGULATORY EVALUATION
=
Background===
The LCOs specify minimum requirements for ensuring safe operation of the facility. When an LCO is not met, the licensee must shut down the reactor or follow any remedial actions permitted by the TSs until the LCO can be met. The TSs typically specify one or more conditions for each LCO, which describe the ways in which the LCO is not met. For each stated condition, the TSs specify one or more required actions (i.e., remediafactions) and associated completion times. Required actions must be completed prior to the expiration of the specified completion time. A condition remains in effect and the associated required actions apply until the condition no longer exists or the unit is not within the LCO applicability.
For each facility, TS Section 1.3, "Completion Times," establishes the completion time convention and provides guidance for its use. The completion time is referenced to the discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an action condition unless otherwise specified. Once a condition has been entered, subsequent trains, subsystems, components, or variables expressed in the condition, discovered to be inoperable or not within limits, will not result in separate entry into the condition, unless specifically stated. The required actions of the condition continue to apply to each additional failure, with completion times based on initial entry into the condition, unless otherwise specified.
The standard technical specifications (STS) provide guidance on the format and content of TSs for each of the light-water reactor nuclear steam supply systems. Second completion times were included in previous versions of the STS for certain systems to ensure that a licensee could not operate indefinitely without meeting the LCO by alternating between different conditions. Second completion times are referenced to the time an LCO is not met rather than the time a condition was entered. The TSs for the licensee's facilities currently include second completion times for some conditions.
TSTF-439, Revision 2, proposed to eliminate the second completion times from the STS. This traveler was approved by the U.S. Nuclear Regulatory Commission (NRC or Commission) by letter dated January 11, 2006 (ADAMS Package Accession No. ML060120272). The current versions of the STS1 incorporate the changes identified in TSTF-439, Revision 2.
2.2 Description of Proposed Changes Based on TSTF-439, Revision 2, the licensee proposed to eliminate second completion times from the TSs for each facility. Currently, Example 1.3-3 in TS Section 1.3 for each facility is used to illustrate the concept of a second completion time (indicated in bold below):
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One Function X A.1 Restore Function 7 days train inoperable.
X train to OPERABLE AND status.
10 days from discovery of failure to meet the LCO B.
One Function Y B.1 Restore Function 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> train inoperable.
Y train to OPERABLE AND status.
10 days from discovery of failure to meet the LCO C. One Function X train C. 1 Restore Function 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable.
X train to OPERABLE AND status.
One Function Y train OR inoperable C.2 Restore Function 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Y train to OPERABLE status.
The licensee proposed to delete the second completion times (i.e., the bold text above) from Example 1.3-3 for each facility. The licensee also proposed to delete the discussions related to 1 NUREG-1430, Revision 4.0, "Standard Technical Specifications: Babcock and Wilcox Plants,"
Volume 1, April 2012 (ADAMS Accession No. ML12100A177); NUREG-1431, Revision 4.0, "Standard Technical Specifications: Westinghouse Plants," Volume 1, April 2012 (ADAMS Accession No. ML12100A222); NUREG-1432, Revision 4.0, "Standard Technical Specifications: Combustion Engineering Plants," Volume 1, April 2012 (ADAMS Accession No. ML12102A165); NUREG-1433, Revision 4.0, "Standard Technical Specifications: General Electric [Boiling-Water Reactor] BWR/4 Plants," Volume 1, April 2012 (ADAMS Accession No. ML12104A192); and NUREG-1434, Revision 4.0, "Standard Technical Specifications: General Electric BWR/6," Volume 1, April 2012 (ADAMS Accession No. ML12104A195).
the second completion times shown in Example 1.3-3. Specifically, the license proposed to delete the following paragraph from TS Section 1.3:
The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10-day Completion Time measured from the time it was discovered the LCO was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. The separate Completion Time modified by the phrase "from discovery of failure to meet the LCO" is designed to prevent indefinite continued operation while not meeting the LCO. This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock." In this instance, the Completion Time "time zero" is specified as commencing at the time the LCO was initially not met, instead of at the time the associated Condition was entered.
The licensee proposed to replace this paragraph with following:
It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.
In addition, the licensee proposed to delete the following statement from TS Section 1.3:
Example 1.3-3 illustrates one use of this type of Completion Time. The 10-day Completion Time specified for Condition A and B in Example 1.3-3 may not be extended.
The licensee also proposed to delete the second completion times associated with the TS required actions listed in the table below:
Plant Technical Specification Required Actions Braidwood TS 3.6.6, "Containment Spray and Cooling Systems" A.1 and C.1 TS 3.8.1, "AC Sources-Operating" A.2 and 8.5 TS 3.8.9, "Distribution Systems - Operating" A.1, 8.1, and C.1 Byron TS 3.6.6, "Containment Spray and Cooling Systems" A.1 and C.1 TS 3.8.1, "AC Sources-Operating" A.2 and 8.5 TS 3.8.9, "Distribution Systems - Operating" A.1, 8.1, and C.1 Clinton TS 3.8.1, "AC Sources-Operating" A.2 and 8.4 TS 3.8.9, "Distribution Systems-Operating" A.1, 8.1, and C.1 Dresden TS 3.8.1, "AC Sources - Operating" A.3 and 8.4 TS 3.8. 7, "Distribution Systems - Operating" A.1 and 8.1 Fitz Patrick TS 3.8.1, "AC Sources-Operating" A.3 and 8.4 TS 3.8.7, "Distribution Systems - Operating" A.1 and B.1 Plant Technical Specification Required Actions LaSalle TS 3.8.1, "AC Sources-Operating" A.3, 8.4, and C.4 TS 3.8.7, "Distribution Svstems-Operatino" A.1 and 8.1 Quad Cities TS 3.8.1, "AC Sources - Operating" A.3 and 8.4 TS 3.8. 7, "Distribution Systems - Operating" A.1and8.1 The licensee's proposed changes included several variations from TSTF-439, Revision 2, which do not affect its applicability. Specifically, the variations include numbering and format differences as well as plant-specific configurations which do not impact the intent of the overall technical justification for the change.
In addition, the licensee proposed to delete an obsolete footnote for a one-time extension of the completion times for required action 8.4 of FitzPatrick TS 3.8.1.
2.3 Regulatory Requirements and Guidance Title 10 to the Code of Federal Regulations (10 CFR) 50.36, "Technical specifications,"
establishes the regulatory requirements related to the content of TSs. Paragraph 50.36(a)(1) requires an application for an operating license to include proposed TSs. A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the TSs.
Pursuant to 10 CFR 50.36, TSs for operating reactors are required to include items in the following five specific categories: ( 1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) surveillance requirements; (4) design features; and (5) administrative controls. In accordance with 10 CFR 50.36(c)(2), LCOs are the lowest
_ functional capability or performance level of equipment required for safe operation of the facility.
When LCOs are not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the LCO can be met.
The STS provide guidance on the format and content of TSs for each of the light-water reactor nuclear steam supply systems. Previous versions of the STS included second completion times for certain required actions to limit the maximum time allowed for any combination of conditions to result in a continuous failure to meet the associated LCO. The second completion times are joined by an "AND" logical connector to the condition-specific completion time and state
"[10 days] from discovery of failure to meet the LCO," where the time in brackets varies by condition. The intent of the second completion time was to preclude entry into and out of the remedial actions for an indefinite period of time without ever meeting the LCO. The second completion time limits the total amount of time the LCO would not be met for various combinations of conditions. TSTF-439, Revision 2, deleted these second completion times from the affected STS required actions.
The current TSs for each facility are based on the improved STS (i.e., NUREG-1430 through NUREG-1434). The Braidwood and Byron TSs are based on NUREG-1431. The Dresden and Quad Cities TSs are based on NUREG-1433. The Clinton TSs are based on NUREG-1434.
The FitzPatrick and LaSalle TSs are based on both NUREG-1433 and NUREG-1434 because these facilities include both General Electric BWR/4 and BWR/6 design elements.
The regulation in 10 CFR 50.65(a)(4) requires the licensee to assess and manage the increase in risk that may result from proposed maintenance activities before performing these activities.
The scope of the assessment may be limited to structures, systems, and components (SSCs) that a risk-informed evaluation process has shown to be significant to public health and safety.
3.0 TECHNICAL EVALUATION
As discussed in Section 2.0 of this safety evaluation (SE), the TSs for the licensee's facilities currently include second completion times for certain required actions to ensure that the licensee could not operate indefinitely without meeting the associated LCO by alternating between different conditions. The licensee proposes to eliminate the second completion times from the TSs for its facilities and replace them with administrative controls. The NRC staff considered the regulations and guidance discussed in SE Section 2.3 in its review of the application.
Prior to the promulgation of 1 O CFR 50.65, TSs provided the primary rules governing operations, including what equipment must normally be in service, how long equipment can be out of service, compensatory actions, and surveillance testing to demonstrate equipment readiness. The goal of TSs is to provide adequate assurance of the availability and reliability of equipment needed to prevent and, if necessary, mitigate accidents and transients. The regulations in 10 CFR 50.65 also support this same goal. In particular, 10 CFR 50.65(a)(4) requires the licensee to assess and manage the increase in risk that may result from proposed maintenance activities before performing these activities.
The application stated, in part:
Under 10 CFR 50.65(a)(4), the risk impact of all inoperable risk-significant equipment is assessed and managed when performing preventative or corrective maintenance. The risk assessments are conducted using the procedures and guidance endorsed by Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." Regulatory Guide 1.182 endorses the guidance in Section 11 of NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." These documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. These include actions to plan and conduct other activities in a manner that controls overall risk, increased risk awareness by shift and management personnel, actions to reduce the duration of the condition, actions to minimize the magnitude of risk increases (establishment of backup success paths or compensatory measures), and determination that the proposed maintenance is acceptable. This comprehensive program provides much greater assurance of safe plant operation than the second Completion Times in the TS.
The second completion times only manage the risk associated with inoperable equipment governed by a single LCO. This is accomplished by limiting the duration in which the plant can continue to operate at power, under certain conditions, without meeting the LCO. However, 10 CFR 50.65(a)(4) requires the licensee to assess and manage the increase in risk that may result from proposed maintenance activities before performing these activities. The management of risk under this regulation is more comprehensive than what is provided by the second completion times because, under the regulation, the licensee must consider the risk impact of all inoperable risk-significant equipment when performing maintenance.
The licensee proposed to delete the second completion times associated with the required actions listed in SE Section 2.2. These second completion times currently prevent repeated entry and exit from required actions without ever meeting the associated LCO. Since the TSs would no longer include second completion times, the licensee also proposed to delete the discussion in TS Section 1.3 related to second completion times. The licensee proposed to add a requirement to TS Section 1.3 to have administrative controls to limit the maximum time allowed for any combination of conditions that result in a single contiguous occurrence of failing to meet the LCO (see SE Section 2.2). These administrative controls would ensure that the completion times for those conditions are not inappropriately extended. The licensee stated that these administrative controls would consider plant risk and be included in plant procedures.
The NRC staff determined that the proposed administrative controls requirement in conjunction with the requirements of 10 CFR 50.65(a)(4) are adequate to limit the duration of a single contiguous occurrence of failing to meet the LCO. These requirements would ensure that the risk associated with equipment inoperability is appropriately managed. In addition, the proposed changes are consistent with TSTF-439, Revision 2. Therefore, the proposed deletion of the second completion times associated with the required actions listed in SE Section 2.2 and the proposed changes to TS Section 1.3 are acceptable to the NRC staff.
The removal of the obsolete footnote for FitzPatrick TS 3.8.1, required action B.4, is acceptable because it is related to a one-time action that is no longer applicable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Illinois and New York State officials were notified of the proposed issuance of the amendments on July 25, 2019. The State officials had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to the installation or use of facility components located within the restricted areas as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the *amounts and no significant change in the types of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding, which was published in the Federal Register on January 30, 2019 (84 FR 493), that the amendments involve no significant hazards consideration, and there has been no public comment on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: C. Tilton, NRR P. Snyder, NRR Date of issuance: October 8, 2 O 1 9
ML19266A527 OFFICE DORL/LPL3/PM NAME BPurnell DATE 10/04/19 OFFICE OGC NLO*
NAME AGhoshNaber DATE 10/04/19 RidsNrrPMByron Resource RidsNrrPMClinton Resource RidsNrrPMDresden Resource RidsNrrPMFitzPatrick Resource RidsNrrPMLaSalle Resource RidsNrrPMQuadCities Resource RidsNrrDssStsb Resource CTilton, NRR PSnyder, NRR
- email DORL/LPL3/LA DSS/STSB/BC(A)*
SRohrer MHamm 9/25/19 9/18/19 DORL/LPL3/BC(A)
DORL/LPL3/PM LRegner (KGreen for)
BPurnell 10/08/19 10/08/19